ML20148J325

Revised Tech Specs 3.6.1 & 4.6.1 Re Surveillance Testing of Personnel Hatch,Electrical Penetrations & Containment Isolation Valves

ML20148J325
Person / Time
Site:	Yankee Rowe
Issue date:	03/09/1977
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20148J312	List: ML20148J307 ML20148J325
References
NUDOCS 8011210684
Download: ML20148J325 (8)

Text

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g CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

b. If any periodic Type A test fails to meet either .75L' or

.75 L the test scheduled for subsequent Type A test $ shall be reviebe,d and approved by the Commission. If two consecutive Type A tests fail to meet either 0.70 L or 0.70 L , a Type A test shall be performed at least every T8 months ubtil two consecutive Type A tests meet either 0.70 L or 0.70 tL at which time the above test schedule may be r$sumed.

c. The accuracy of each Type A test shall be verified by a

. supplemental test which requires the metered mass of gas injected into the containment or bled from the containment for the supplemental test to be equivalent to between 50 and 100% of the allowable 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mass loss. The acceptability is demonstrated if the mass change, as measured by the Type A instrumentation, agrees with the mass change as metered by the -l

^ flow meter to within 25'4 of the allowable 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> mass loss, l

d. Type B and C tests shall be conducted with gas at P , 31.6 psig, at interval.s no greater than 24 months except for t$sts involving the air lock, the equipment halt h, the emergency hatch, the containment leg expansion joints, and the fuel chute expansion

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joint.

e. 25% of all electrical penetrations shall be locally leak tested annually subject to the following conditions:

1) During testing of the electrical penetrations, any penetration which f ails the. leak test shall be included in the subsequent annual tests until two acceptable .

consecutive leak tests have been demonstrated, and

2) these penetrations shall be additional to the 25% selected for testing during the subsequent annual test periods.

f. The air lock shall be tested and demonstrated OPEPABLE per Specification 4.6.1.3.

g. The equipment and emergency hatch seals and seating surfaces shall be inspected before each hatch closure.

h. All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to provide a maximum expected error.

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. CONTAINMENT SYSTEMS .

CONTAINMENT AIR LOCK' I

LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air _ lock 'shall be 0PERABLE with: ]

a. Both' doors closed except when the' air lock is being used for.

normal-transit entry and exit through the containment, then at least one air lock door shall be closed, and

-b. An overall air _ lock leakage rate of < 0.05 L, at P,, 31.6 psig.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION With the air lock inoperable,. restore-the air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STAMDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

. SURVEILLANCE REQUIREMENTS 4.6.1.3 The containment air lock shall be demonstrated OPERABLE:

s a. By leak testing the door seals and seating surface within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening, or when the air lock is being used for multiple entries, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first of the series of openings.

b. At least once per 6 months by conducting an overall air lock leakage test at P 31.6 psig, and by verifying that the overall air lock leakage fa,te is within its limit, and

c. At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

i YANKEE-ROWE 3/4 6-4 i.g

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TABLE 3.6-1 (Continued)' ,

CONTAINMENT ISOLATION VALVES _

TESTABLE DURING .

VALVE NUMBER FUNCTION PLANT OPERATION . ISOLATION TIME-

g .(Yes or No) Seconds z B. Manual Valves m

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SC-MOV-551+553* Shutdown Cooling - In _ No .NA : .

y SC-MOV-552+554* Shutdown Cooling - Out No NA m ..

CH-MOV-522* MC Feed to Loop Fill Header NA NA CS-V-601 Shield Tank Cavity Fill NA NA . b .t --

CA-V-746* Containment Air. Charge NA NA HV-V-5 Containment H2 Vent System No NA .

HV-V-6 Containment H2 Vent System No NA CA-V-688 Containment H2 Vent System Air Supply NA NA

$ CS-M0V-500 Fuel Chute Lock Valve No NA h

f. *Not subject to Type C tests

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5 TABLE 3.6-1 (Continued) ' .

CONTAINMEtiT ISOLATION VALVES ,

y TESTABLE DURING E VALVE NUMBER FUNCTION PLANT OPERATION ISOLATION TIME (Yes or No) Seconds m

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=c B. Manual Valves (Cont'd) .

CS-CV-215 Fuel Chute Equalizing NA NA --

CS-CV-216 Fuel Chute Dewatering NA NA. ~O' Pump Discharge VD-V-752* Neutron Shield Tank-Outer Test NA NA VD-V-754* Neutron Shield Tank-Inner Test NA NA BF-V-4-1 Air Purge Inlet NA 'NA BF-V-4-2 NA NA

R Air Purge Outlet HC-V-602 Air Purge Bypass Nn NA PU-MOV-543 ECCS Recirculation Yes 50 PU-M0V-544 ECCS Recirculation Yes 50 Main Coolant Heise Pressure Gauge NA NA

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3/4.6 CONTAINMENT SYSTEMS _

BASES 1

._ 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAIllMENT INTEGRITY ensur'es that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated. leak rates assumed in the accident analyses.

This. restriction, in conjunction with the leakage rate limitation, will l imit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

Containment fntegrity is not ' required with Main Coolant System temperature < 200 F or pressure < 300 psig because no_ steam will be generated in the unlikely event of a Main Coolant System rupture and hence, no driving force to release fission products from the containment will exist.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containn'ent leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P . As an added conservatism,the'measuredoverallintegratedleak$gerateisfurther limited to < 0.70 L or 0 the periodE test t8 accou.70 L , as applicable, during performance e leakage barriers between leakage tests. ,

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50, 3/4.6.1.3 CONTAIUMENT AIR LOCK The limitations on closure and leak rate for the containment air lock are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. The intermediate tests of the containment airlock "J" of 10 CFR 50.

seals are for conformance with the requirements of Appendix YANKEE-ROWE B3/4 6-1 s

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3/4.6.1.4 -INTERNAL PRESSURE l The. limitations on containment internal pressure ensure that the . .!

containment peak pressure does not exceed the design pressure of 34.5  ;

psig during LOCA conditions. z The maximum peak pressure expected to be obtained~from a LOCA event i is' 31.6 psig. .The limit of 3.0 psig.for initial positive containment pressure will limit the total pressure to 31.6 psig which is,less than .

the design pressure and is consistent with the accident analyses. .

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,' 3/4.6.1.5 AIR TEMPERATURE ,

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The limitations on. containment. average air temp'erature ensure.t. hat- i the overall containment average air temperature does not exceed the -

initial temperature condition. assumed in the accident analysis for a LOCA.

The average air temperature is determined in accordance with the following equation:

Average air temperature = (each loop temperature x 6) plus (charging  ;

floor temperature x 20) plus (each hemisphere, low, temperature x'8) plus (each hemisphere, fen, temperature x 20) divided by 100.

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. CONTAINMENT SYSTEMS -

BASES 2/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY-This'1 imitation ensures tha't the structural integrity. of the containment will be maintained comparable to the original design standards for the life of the facility. Structurel integrity is required to ensure that the containment will withstand the maximum pressure of 31.6 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.

3/4. 6.1.7 CONTINUOUS LEAK MONITORING SYSTEM The OPERABILITY of the continuous leak monitoring system provides some assurance that the containment equipment hatch seal, emergency hatch seal, containment leg expansion joints, fuel chute expansion joints and electrical penetrations are not leaking excessively between Type A leak ~ tests.

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3/4.6.2 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will b'e isoiated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

3/4.6.3 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection .

and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. The purge system is capable of controlling the expected hydrogen generation associated with 1) zirconiuni-water reactions,

2) radiolytic decomposition of water and 3) corrosion of metals within contain-ment.

The hydrogen recirculating system is provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent . localized accumulations of hydrogen from exceeding the flammable ,

limi t.

W YANKEE-ROWE B 3/4 6-3 N

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u.s. NUCLE AR RECULATCRY Cf MVisSl!N DOCKET NyM BE R e.. . . . , ,

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• hjRC DISTRIBl1'h0N FoR PART 50 DOCKET MATERIAL TO: NRC., '* FROM: YAEC DATE OF DOCUMENT Westborough, Mass. 01581, 3-9-77

, D.E. Vandenburgh , DATE RECElVED , .

3-16-77 -

R ETTER ENOTORIZED - P R OP, INPUT FORM NUMBER OF COPlES RECEIVED CORIGIN AL - - SUN'CLASSIFIE D 3Si@W C3Cory .

l DESCRIPTION Ltr notarised 3-9-77 requesting for ENCLOSU RE Proposedtechspeechanges..[-(9P) l Pr: posed Change No. 149 to Tech Specs dealini; ,

with surveillance testing of electrical -

pInetration to the containment & trans the fellowens: (3P) -

- Y 9050 0 i .

p oinED # ' '

PLANT NAME: Yankee Rode '

SAFETY FOR ACTION /INFORMATION FwTun -

ASSIGNED AD: , .

AngTcu n An.

)MNCH CHIEFt SCh W M,s,>[C] M AMM EMTFP.

PR0 JECT MANAGERr 8 b b c e,4- . PROJECT MANAGER:

/ LIC. ASST. S Q Ja.V d. LIC. ASST.

C INTERNAL DISTRIBUTION

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SYSTEMS SAFETY PLANT SYSTFMS

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SITE SAFETY &

G muT~PDB . HEINEMAN TEDESCO ENVIRO ANALYSTS

/ ,I & E ( ~3.) SCHROEDER BENAROYA DENTON & Mtif.FR

/ OELD LATNAR

/ GOSSICK & STAPF ENGINEERING IPPOLITO ENVIRO TECH.

MIPC MACARRY KIRKWOOD ERNST CASE  !!0SNAK BALLARD HANAUER SI1NEIL OPERATING REACTORS YOUNGBLOOD HARLESS PAWLICKI STELLO SITE TECH.

PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH. CAMMILL BOYD ROSS /' EISENHUT STEPP P, COLLINS NOVAK / SHA0 HULMAN HOUSTON ROSZTOCZY G BAER PETERSON CHECK I, BUTLER SITE ANALYSIS l MELTZ / CBIMES VOLLMER l HELTEMES AT & I BUNCH l SKOVHOLT SALTZMAN /J. COLLINS l RUTBERG KREGER i

,, , EXTERNAL DISTRIBUTION CONTROL NUMBER lLPDR: G 6ea Aff e, f d. ,,H/40 AT. LAB: BR00KHAVEN 3AT. LAB.

TIC: REG V.IE ITLEIKSON (ORNL)

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[ESIC: LA PDR

• ASLB:, CONSULTANTS: - # 7707 M Y 7ERS/6 CYS aieterne/ sEo r45 cwa NRCFORM 195(2 76) ~

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